MERCSF-N: A program for the calculation of fast neutron removal cross sections in composite shields

Influence of Boron Carbide Addition on Performance and Neutron Shielding Ability of Cement Mortar Mix

“…The macroscopic removal cross section value as a whole for a specimen is calculated by the programme [11] .To calculate this, the individual elemental composition is obtained by EDS analysis. The values obtained from this test is taken at a constant magnification for all specimen, and also the non-uniform distribution of 15 micron size boron carbide crystal and other components of the mix significantly varies the macroscopic removal cross section of the specimen in whole.…”

“…The macroscopic cross-section represents the effective target area of all of the nuclei contained in the volume of the material. The calculation of removal cross section analysis can be carried out in cases where the specimen cannot be experimentally tested in the nuclear facility [11,19] . It is observed that there is a 10% deviation in the values when calculated using the empirical formula than with experimentally found out results.…”

“…The neutron attenuating property of a material can be experimentally determined by testing in the sophisticated nuclear radiation setup in radioactive research centers [15] . These observations can also be mathematically calculated using some verified hand calculation methods with the help of standard available microscopic cross section value database for element [19] , compound and other materials or by software based calculation analysis like Monte Carlo analysis etc., and hence determining the comprehensive macroscopic cross section values of the sample [11] . The present paper reports the work done using B 4 C in cement mortar to enhance its neutron shielding capacity which is analysed by removal cross section study.…”

The Role of Replacing CdO by Fe<sub>2</sub>O<sub>3</sub> on the Fast Neutron Removal Cross Sections in Cd-Boro Phosphate Glass Shield

“…. The description and validation, as well as, the use of the MERCSF-N program have been described [21]. The definition of the Σ R in accordance with Equation (1) is dependent on the elemental composition of a shielding material.…”

Development of alkali activated borosilicate inorganic polymers (AABSIP)

“…In contrast, the isotopes that best capture lower energy (thermal) neutrons are those with high microscopic absorption cross-sections, however this property does not vary smoothly with atomic mass. 18,19 Elements with stable isotopes with particularly high absorption cross-sections include 20 : B, Rh, Cd, In, Pm, Sm, Eu, Gd, Dy, Er, Tm, Hf, Ir, Au, Hg, Pa, Np. Hydrogenous material is often used to slow down high energy (fast) neutrons so that they can interact with the other isotopes in the shielding.…”